ARIANT Assessments for CANDU Analysis Using RD-14M Experiments
ARIANT (AlgoRIthm for Analysis of Network Thermalhydraulics) is a Canadian Nuclear Laboratories system thermal-hydraulic code for the modeling and analysis of two-phase flow and heat transfer for pressurized heavy water reactors, light water pressurized water reactors, and advanced reactor applications. This paper presents ARIANT models and simulations of RD-14M experiments, including small-break loss-of-coolant accidents, large-break loss-of-coolant accidents, loss-of-flow accidents, station blackout, and natural circulation, that are representative of accident scenarios in a CANDU reactor.
Authors
- Shujun Wang (ORCID: https://orcid.org/0000-0003-4377-2791)
- Geoffrey Waddington
- Songyu Liu (ORCID: https://orcid.org/0000-0002-8135-3806)
- John Cui
Institutions
- Canadian Nuclear Laboratories (CA)
Publication Details
- Journal
- Nuclear Science and Engineering
- Published
- 2024-08-19
- DOI
- https://doi.org/10.1080/00295639.2024.2380628
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 0.00